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International Research Progress on Nuclear Waste Vitrification: A Review(PDF)

MATERIALS CHINA[ISSN:1674-3962/CN:61-1473/TG]

Issue:
2016年第07期
Page:
21-25
Research Field:
特约研究论文
Publishing date:

Info

Title:
International Research Progress on Nuclear Waste Vitrification: A Review
Author(s):
XU Kai
Division of Advanced Nuclear Engineering, Department of Materials Science and Engineering, Pohang University of Science and Technology-POSTECH
Keywords:
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CLC:

PACS:
-
DOI:
10.7502/j.issn.1674-3962.2016.07.01
DocumentCode:

Abstract:
Vitrification is the well-developed and the only kind of technology to industrially immobilize the nuclear wastes originating from civil and military spent fuel reprocessing, because the glass waste form enables to incorporate a very large range of elements, has the good long-term durability to resist the chemical corrosion, and could be produced with the relative simple processes under the remote control. In the view point of materials science and technology, this paper introduced the glass immobilization mechanism and principles to design glass waste form, and then reviewed the recent international research progress on glass waste form. The main efforts includes (i) ability to accommodate the waste to improve the waste loading, (ii) melter feed reactions to maximize the rate of melting, and (iii) the corrosion mechanism and the long-term behavior to ensure the safe disposal. Finally, future trends and options in waste vitrification were prospected.

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Last Update: 2016-06-29